P Rullhusen IAEATM on Nuclear Data Library for
P. Rullhusen IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007 Nuclear data for fusion applications an experimentalist's view Peter Rullhusen peter. rullhusen@ec. europa. eu 1
P. Rullhusen IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007 potential nuclear data needs ITER: – diagnostics – activation (FW, BM, Div, vac. vessel, bio shielding) IFMIF: – d-induced reactions – n-induced reactions up to 60 Me. V • shielding • radiation dammage DEMO: – ch. p. induced reactions (d, t, 3 He, . . . ) – n-induced reactions up to 20 Me. V 2
P. Rullhusen IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007 diagnostics: for example: work carried out at IRMM in collab. with JET activation measurements spectroscopy, partly in underground laboratory HADES the following slides have been borrowed from a presentation at IRMM by G. Bonheure Plasma Physics Laboratory Brussels, Belgium 3
presentation G. Bonheure 28/09/2007 at IRMM P. Rullhusen 4 IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007 ITER: Many engineering challenges Change of extent of fusion research. Many new problems to solve. Millions of parts with very complex interfaces Extremely high heat fluxes in first wall components, & materials under neutron irradiation Unprecedented size of the super-conducting magnet and structures MAST JET ITER. Major radius (m) 0. 9 3 6. 1 Aspect ratio 1. 3 2. 5 3. 0 Plasma current (MA) 1. 4 4. 8 15 Toroidal field (T) 0. 5 3. 5 5. 3 Fusion power (MW) -(16) 500 Pulse length (s) ~2 ~10 >1000 Q <<1 ~1 >10. Divertor module Blanket module
presentation G. Bonheure 28/09/2007 at IRMM P. Rullhusen IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007 Access: ITER diagnostics are port-based where possible Each diagnostic port-plug contains an integrated instrumentation package 5
presentation G. Bonheure 28/09/2007 at IRMM P. Rullhusen 6 IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007 Neutron diagnostic systems: 4 types of systems Time-resolved total emission (non-collimated flux) Fusion power Time-integrated emission (fluence) Absolute emission Calibration of time-resolved emission 2 D-cameras (collimated flux along camera viewing lines) Spatial distribution of emission tomography Spectrometers (collimated flux along radial and tangential viewing lines) Plasma temperature and velocity Plasma density Combination of these measurements characterizes the plasma as a neutron source
presentation G. Bonheure 28/09/2007 at IRMM P. Rullhusen IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007 1. Time-resolved neutron emission Fission counters: – 238 U and 235 U counters embedded in moderator and led shield – Operate both in counting and current mode – Dynamic range: excellent (10 orders of magnitude) – 3 pairs installed at different positions around JET – Low sensitivity to X and radiation – No discrimination between 2. 5 and 14 Me. V neutron emission – Calibrated originally in situ with californium 252 Cf neutron source, periodically recalibrated using activation technique 7
presentation G. Bonheure 28/09/2007 at IRMM P. Rullhusen IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007 8 2. Time-integrated neutron emission Neutron activation method Samples used as flux monitors are automatically transferred to 8 Irradiation ends Sample activity measurements: 1) gamma spectroscopy measurements >>> most widely used reactions at JET: DD neutrons - 115 In(n, n’)115 m. In, DT neutrons - 28 Si (n, p)28 AL, 63 Cu(n, 2 n)62 Cu, 56 Fe(n, p)56 Mn >>> detectors : 3 Na. I, HPGe (absolutely calibrated) 2) delayed neutron counting (235 U, 238 U, 232 Th) >>>detectors: 2 stations with six 3 He counters Calibration: accuracy of the time-resolved measurements is typically ~ 8 -10% for both DD and DT neutrons (7% at best using delayed neutron method) – after several years of work !!
presentation G. Bonheure 28/09/2007 at IRMM P. Rullhusen IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007 Other fusion products measurements Confined fast ions and fusion products Losses of fast ions and fusion products d+d p (3024 ke. V) d + 3 He p (14681 ke. V) + (3670 ke. V) d+d n (2450 ke. V) d+t n (14069 ke. V) + (3517 ke. V) + ICRF accelerated ions + t (1008 ke. V) + 3 He (817 ke. V) 9
presentation G. Bonheure 28/09/2007 at IRMM P. Rullhusen 10 IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007 How to measure confined ions with gammas? Detection of -ray lines due to nuclear reactions with fuel and with the main plasma impurities, Be and C protons D(p, )3 He T(p, )4 He 9 Be(p, )10 B 9 Be(p, p’ )9 Be 9 Be(p, )6 Li 12 C(p, p’ )12 C Fast scintillators La. Br 3 : Ce (known as Bril. Lan. Ce): • Light yield 60, 000 photons/Me. V • Energy resolution - better than 3% • Decay times - < 20 ns (Na. I: 250 ns) LYSO: • Decay time 40 ns • Better light output ( 32, 000 photons/Me. V ) • Slightly radioactive ( - and - radiation) BGO Na. I(Tl) BGO
presentation G. Bonheure 28/09/2007 at IRMM P. Rullhusen IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007 11 Activation probe • • SAMPLES activation by charged particles ANGULAR DISTRIBUTION (v magnetic field) of radionuclides : anisotropic for charged particles Absolute measurements of time-integrated losses of charged particles Recent results from D – 3 He plasmas 10 B (p, α) 7 Be , 7 Li (p, n) 7 Be Detection of 14. 6 Me. V protons from threshold reaction 48 Ti(p, n)48 V Eth : 5 Me. V
P. Rullhusen IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007 12 diagnostics (cont. ) work carried out at IRMM in collab. with JET: activation of Ti, Mg. F 2 and Ti. VAl alloy ( spectr. partly in underground lab) J. Gasparro et al. , Appl. Rad. Isot. 64(2006) , G. Bonheure et al. , Phys. Scr. 75 (2007) 769
P. Rullhusen IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007 diagnostics (cont. ) activation of Ti, Li. F, B 4 C and W ( spectr. partly in underground lab) E. Wieslander et al. , to be publ. 13
P. Rullhusen IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007 ITER activation, rad. damage. Example: materials under consid. for Blanket Module Be Al Cu Cr Zr Ti SS inconel 14
P. Rullhusen IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007 structural materials D. L. Smith, Neutron Reaction Data for IFMIF: example Fe 15
P. Rullhusen IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007 16 Summary: what IRMM can contribute n-induced reactions: – Vd. G: En ~ 1 Me. V – 25 Me. V – ch. p. induced reactions (p, d, ): up to 7 Me. V (t, x) look for inverse reactions – activation: half-lives > 10 min (external); very long: HADES ~ 10 ms – 1 s (beam chopper 1 Hz – 5 k. Hz) – high-resolution TOF: total, capture, (n, n') , (n, 2 n) with installation of new ECR source (end 2007): – optimised for H, D, He+ and He++ at i>60 m. A – possibility of accelerating 3 He, 6 Li (to be investigated) proposed: 200 m. A, 2 MV singletron for high-intensity measurements at low energies
P. Rullhusen IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007 what IRMM can do (cont. ) example: recent activ. meas. on W isotopes V. Semkova, A. Plompen 182 W(n, p)182 Ta, 183 W(n, x)182 Ta 183 W(n, p)183 Ta, 184 W(n, x)183 Ta, 183 W(n, n')183 m. W 184 W(n, )181 Hf, 184 W(n, p)184 Ta, 184 W(n, 2 n)183 m. W 186 W(n, )183 Hf, 186 W(n, x)185 Ta, 186 W(n, p)186 Ta, 186 W(n, 2 n)185 m. W 17
P. Rullhusen IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007 what IRMM can do (cont. ) example: upcoming capture and transmission meas. on W isotopes NUDAME proposal: 18
P. Rullhusen IAEA-TM on Nuclear Data Library for Advanced Systems - Fusion 31 Oct. – 2 Nov. 2007 what IRMM can do (cont. ) FNG expt. for FENDL validation (contr. P. Batistoni): Si, Nb, Ni, Fe, Sr, Al: which reactions? which enenergy range? Be/Li 2 CO 3 breeder: 9 Be(n, n) 9 Be(n, 2 n) n angular distribution: new set-up for elast. scatt. only cross sections remark: NRG (A. Hogenbirk) presented at NEMEA-4 workshop a method to carry out uncertainty calculations in arbitrary 3 D geometries using MCNP as a radiation transport code. 19
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